Microstructural evaluation and Ring compression testing of nuclear grade stainless steel fuel claddings

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Microstructural evaluation and Ring compression testing of nuclear grade stainless steel fuel claddings

Popis výsledku v původním jazyce

Fuel claddings act as first metallic barriers against loss of fission products during the reactor operation, intermittent storage or final dry storage. Their integrity is critical for the safe operation of power plants. To assess the claddings structural integrity, comprehensive characterization of microstructure and mechanical properties is necessary. In this work, recently produced nuclear grade stainless steel cladding material, cold worked at 24 % and 46 % microstructural analysis was performed. Microscopic investigations revealed the presence of Ti-(C,N) precipitates at the sub-micrometer range and a few larger precipitates up to several microns. Elongated stringer like TiC precipitates in the tube drawing direction were also revealed. Grain size was determined and a well-defined substructure was observed in Field Emission Gun Scanning Electron microscopy (FEG-SEM) and High Resolution Transmission Electron Microscopy (HR-STEM) with characteristic features as MC precipitates, twins, micro-twins, slip bands. No significant microstructural variance between the two cold worked materials was observed. Fuel cladding mechanical properties are assessed by number of testing techniques and evaluating methodologies. There is no standard for testing of fuel claddings due to their geometry (tubular) and smaller wall thickness (app. 0.6 mm). In this work, ring compression test method has been applied to assess stainless steel cladding mechanical properties at room temperature. Methodology and preliminary results from the ring compression tests are presented.

Název v anglickém jazyce

Microstructural evaluation and Ring compression testing of nuclear grade stainless steel fuel claddings

Popis výsledku anglicky

Fuel claddings act as first metallic barriers against loss of fission products during the reactor operation, intermittent storage or final dry storage. Their integrity is critical for the safe operation of power plants. To assess the claddings structural integrity, comprehensive characterization of microstructure and mechanical properties is necessary. In this work, recently produced nuclear grade stainless steel cladding material, cold worked at 24 % and 46 % microstructural analysis was performed. Microscopic investigations revealed the presence of Ti-(C,N) precipitates at the sub-micrometer range and a few larger precipitates up to several microns. Elongated stringer like TiC precipitates in the tube drawing direction were also revealed. Grain size was determined and a well-defined substructure was observed in Field Emission Gun Scanning Electron microscopy (FEG-SEM) and High Resolution Transmission Electron Microscopy (HR-STEM) with characteristic features as MC precipitates, twins, micro-twins, slip bands. No significant microstructural variance between the two cold worked materials was observed. Fuel cladding mechanical properties are assessed by number of testing techniques and evaluating methodologies. There is no standard for testing of fuel claddings due to their geometry (tubular) and smaller wall thickness (app. 0.6 mm). In this work, ring compression test method has been applied to assess stainless steel cladding mechanical properties at room temperature. Methodology and preliminary results from the ring compression tests are presented.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2016

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Utilization of SUSEN Technologies for the Gen IV Development

ISBN

978-80-270-0925-1

ISSN

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e-ISSN

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Počet stran výsledku

7

Strana od-do

92-98

Název nakladatele

Centrum výzkumu Řež, s.r.o.

Místo vydání

Řež

Místo konání akce

Řež

Datum konání akce

24. 11. 2016

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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